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| {{#Wiki_filter:ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 | | {{#Wiki_filter:}} |
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 PREPARED BY / DATE: 1/16/19 David Montt, Radiological Engineer REVIEWED BY / DATE: ___ ___________1/22/19 Robert Massengill, Radiological Engineer APPROVED BY / DATE: ______________________________________
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| 1/23/2019 D. Wojtkowiak, C/LT Manager
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| [2]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 TABLE OF CONTENTS
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| : 1. EXECUTIVE
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| ==SUMMARY==
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| ................................................................................................ 5
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| : 2. SURVEY UNIT DESCRIPTION ...................................................................................... 6
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| : 3. CLASSIFICATION BASIS ............................................................................................... 9
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| : 4. DATA QUALITY OBJECTIVES (DQO) ...................................................................... 10
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| : 5. SURVEY DESIGN ........................................................................................................... 14
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| : 6. SURVEY IMPLEMENTATION .................................................................................... 18
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| : 7. SURVEY RESULTS ........................................................................................................ 19
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| : 8. QUALITY CONTROL .................................................................................................... 26
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| : 9. INVESTIGATION AND RESULTS .............................................................................. 27
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| : 10. REMEDIATION AND RESULTS.................................................................................. 27
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| : 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ...................................... 27
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| : 12. DATA QUALITY ASSESSMENT (DQA) ..................................................................... 27
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| : 13. ANOMALIES ................................................................................................................... 28
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| : 14. CONCLUSION ................................................................................................................. 28
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| : 15. REFERENCES ................................................................................................................. 28
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| : 16. ATTACHMENTS ............................................................................................................. 29 ATTACHMENT 1 FIGURES AND MAPS ........................................................................30 ATTACHMENT 2 ISOCS GEOMETRY............................................................................33 ATTACHMENT 3 SIGN TEST ..........................................................................................40 ATTACHMENT 4 QC MEASUREMENT ASSESSMENTS ............................................43 ATTACHMENT 5 EBERLINE REPORT ..........................................................................48 ATTACHMENT 6 ISOCS ANALYTICAL REPORTS......................................................73
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| [3]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 LIST OF FIGURES Figure 1 - Unit 1 East and 2 West Main Steam Valve Houses ....................................................... 7 Figure 2 - Unit 1 East Main Steam Valve House Detail ................................................................. 8 Figure 3 - Unit 1 West Main Steam Valve House Detail ............................................................... 9 Figure 4 - Unit 1 East Main Steam Valve House ISOCS Survey and Sample Map ..................... 20 Figure 5 - Unit 1 West Main Steam Valve House ISOCS Survey and Sample Map ................... 21 LIST OF TABLES Table 1 - Dose Significant Radionuclides and Mixture ................................................................ 11 Table 2 - Base Case DCGLs (DCGLB) from LTP Chapter 5, Table 5-3 ...................................... 12 Table 3 - Operational DCGLs (DCGLB) from LTP Chapter 5, Table 5-4 ................................... 13 Table 4 - Surrogate Ratios ............................................................................................................ 15 Table 5 - Investigation Levels....................................................................................................... 16 Table 6 - Synopsis of the Survey Design ...................................................................................... 17 Table 7 - Unit 1 East Main Steam Valve House- ISOCS Results for FSS ................................... 22 Table 8 - Basic Statistical Properties of ISOCS Measurements in the Unit 1 East Main Steam Valve House ............................................................................................. 23 Table 9 - Unit 1 West Main Steam Valve House- ISOCS Results for FSS .................................. 23 Table 10 - Basic Statistical Properties of ISOCS Measurements in the Unit 1 West Main Steam Valve House ........................................................................................... 24 Table 11 - FSS Concrete Core Taken in East Main Steam Valve House Analysis by Eberline .. 25 Table 12 - FSS Concrete Core Taken in West Main Steam Valve House Analysis by Eberline . 25 Table 13 - Summary of ISOCS Replicate Measurements for QC Unit 1 East Valve House ....... 26 Table 14 - Summary of ISOCS Replicate Measurements for QC Unit 1 West Valve House ...... 27
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| [4]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
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| : 1. EXECUTIVE
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| ==SUMMARY==
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| This Final Status Survey (FSS) Release Record for Survey Units #B1-06213 and #B1-06214, Unit 1 East and West Steam Tunnel Valve Houses, was generated for the Zion Station Restoration Project (ZSRP) in accordance with ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the Zion Station Restoration Project License Termination Plan (LTP, Reference 2).
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| The FSS Sample Plans for Survey Units #B1-06213 and #B1-06214 were developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference 3) the ZSRP LTP, and guidance from NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4).
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| Final Status Survey was performed on the Unit 1 East and West Steam Tunnel Valve Houses to demonstrate that the concentrations of residual radioactivity were equal to or below site-specific Derived Concentration Guideline Levels (DCGL) corresponding to the dose criterion in 10 CFR 20.1402. In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the Turbine Building survey unit has a MARSSIM classification of 3. The Unit 1 East and West Steam Tunnel Valve Houses were re-classified as a Class 1 due to the discovery of radioactive material concentrations in excess of the Operational DCGLs (OpDCGL) from ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for FSS (Reference 5) during the performance of the FSS.
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| A Sample Plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II () decision error rates were set at 0.05. The Canberra In Situ Object Counting System (ISOCS) and was selected as the primary instrument used to perform FSS. To ensure 100% of the surface area was surveyed in accordance with the classification, twenty-six (26) ISOCS measurement locations were selected in each Valve House (for a total of 52 measurements) using several adjusted Field-of-View (FOV) geometrys as specified in ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Source Term Survey of End State Structures (Reference 6).
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| The results of the FSS showed that the Sum-of-Fractions (SOF) for 49 of the 52 ISOCS measurements taken was less than one (1) when applying the respective OpDCGL for the Turbine Building basement. Three (3) ISOCS measurements exceed the OpDCGL but were below the Base Case DCGLs (BcDCGL). The mean concentration for each ROC was below the BcDCGL and the survey unit passed the Sign Test. Therefore, the null
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| [5]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 hypothesis is rejected and the Unit 1 East and West Steam Tunnel Valve Houses are acceptable for unrestricted release.
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| : 2. SURVEY UNIT DESCRIPTION Both the Unit 1 East and West Steam Tunnel Valve Houses were located on the 570 foot elevation and housed the East and West Main Steam Valves. The Valve houses were adjacent to each of the Containment buildings (see Figures 1, 2 and 3) on the East and West sides of Unit 1 with a mirror image of that footprint for Unit 2. The entrances into the Unit 1 East and West Steam Tunnel Valve Houses were from each of the Main Steam Tunnels leading to each respective containment structure Valve House at the Turbine Building 570 foot elevation (See Figure-1, 2 and 3). The surface area of each of the Unit 1 Valve House structural survey units is 304 m2.
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| [6]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Figure 1 - Unit 1 East and 2 West Main Steam Valve Houses Unit 1 West MS Unit 2 West MS Valve House Valve House Unit 1 East MS Unit 2 East MS Valve House Valve House North
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| [7]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Figure 2 - Unit 1 East Main Steam Valve House Detail Unit 1 East MS Valve House
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| [8]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Figure 3 - Unit 1 West Main Steam Valve House Detail Unit 1 West MS Valve House
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| : 3. CLASSIFICATION BASIS Survey Unit #06100 (Turbine Building) was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 7). In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the Turbine Building survey unit was assigned a MARSSIM classification of 3. In April of 2016, an FSS was conducted on the Turbine Building basement structure. The surface area of the Unit 1 East and West Steam Tunnel Valve Houses was included with the Turbine Building for the DCGL calculation however, the surface area was not included in the FSS of the Turbine Building basement. In addition, the demolition of the Valve Houses occurred two years after the demolition of the Turbine Building basement. Consequently, a separate FSS was required of the Valve Houses prior to backfill.
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| [9]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 The Unit 1 East and West Steam Tunnel Valve Houses were classified, as the Turbine Building, in accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 as a Class 3 survey unit. A final classification assessment was performed in accordance with procedure ZS-LT-300-001-002 as part of the survey design for FSS. Upon completion of Survey Unit Classification basis for final classification, which included a review of the Zion Station Historical Site Assessment (HSA) (Reference 8), the classification for survey design remained as Class 3. During the performance of FSS, it was observed that many survey measurements exceed 50% of the OpDCGLs and several exceeded a SOF of one.
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| Consequently, the Unit 1 East and West Steam Tunnel Valve Houses, Survey Units #B3-06213 and #B3-06214 were reclassified from a Class 3 to a Class 1 survey unit and the survey was redesigned accordingly.
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| The FSS Radiological Engineer (RE) performed a visual inspection and walk-down of the survey unit on 04/19/2018 prior to performing FSS. The purpose of the walk-down was to evaluate and assess the physical condition of the survey unit, access points, travel paths and identify potentially hazardous conditions.
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| : 4. DATA QUALITY OBJECTIVES (DQO)
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| Final Status Survey planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objectives of the survey is satisfied. The DQO process is described in the ZSRP LTP. The appropriate design for a given survey is developed using the DQO process as outlined in Appendix D of MARSSIM.
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| The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis.
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| Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan.
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| The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in Survey Units #B1-06213 and #B1-06214 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).
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| [10]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ZionSolutions TSD 11-001, Potential Radionuclides of Concern during the Decommissioning of Zion Station (Reference 9) established the basis for an initial suite of potential ROC for the decommissioning of the Zion Nuclear Power Station (ZNPS).
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| LTP Chapter 2 provides detailed characterization data that described contamination levels in the basements. Concrete core samples, collected during characterization surveys, were obtained at biased locations where there were elevated contact dose rates and/or evidence of leaks/spills. The collected core samples were analyzed for the presence of plant-derived radionuclides.
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| LTP Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. LTP section 6.5.2 also states that the Auxiliary Basement ROC and the IC percentage of 5% for adjusting ROC DCGLs will also be applied to all other Basements including those for the Main Steam Valve Houses unless different values are justified by the results of continuing characterization or FSS HTD analysis.
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| Table 1 presents the ROC for the Auxiliary Basement and, therefore, the Valve House structural surfaces and the normalized fractions based on the radionuclide mixture.
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| Table 1 - Dose Significant Radionuclides and Mixture
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| % of Total Activity Radionuclide (normalized)(1)
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| Co-60 0.92 Cs-134 0.01 Cs-137 75.32 Ni-63 23.71 Sr-90 0.05
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| : 1. Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides.
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| A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures.
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| The End State Basements will be comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the BFM are associated with residual radioactivity in floors and walls released through leaching into water contained in the interstitial spaces of the fill material. The BFM assumes that the inventory of residual radioactivity in a given
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| [11]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 building is released either instantly or over time by diffusion, depending on whether the activity is surficial or volumetric, respectively. The activity released into the fill water will adsorb onto the clean fill, as a function of the radionuclide-specific distribution coefficients, resulting in equilibrium concentrations between the fill and the water.
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| Consequently, the only potential exposure pathways after backfill, assuming the as-left geometry, are associated with the residual radioactivity in the water contained in the fill.
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| The final outputs of the BFM are the Basement DCGL, in units of pCi/m2, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors (LTP Chapter 6, Tables 6-24 and 6-25). The DCGLs for basement structure surfaces are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the Base Case DCGL and is used during FSS to demonstrate compliance (analogous to the DCGLW as defined in MARSSIM). The Base Case DCGLs are radionuclide-specific concentrations that represent the 10 CFR 20.1402 dose criterion of 25 mrem/year and are calculated for each ROC and each backfilled Basement.
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| When applied to structures, the DCGLs are expressed in units of activity per unit of area (pCi/m2). The unity rule is applied when there is more than one ROC. The measurement results for each singular ROC present in the mixture are compared against their respective DCGL to derive a dose fraction.
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| The Base Case DCGLs for the unrestricted release of the Turbine Building (including the Main Steam Valve houses) are provided in Table 2. The Insignificant Contributor (IC) dose percentage of 5% was used to adjust the Turbine Building Base Case DCGLs to account for the dose from the eliminated IC radionuclides.
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| Table 2 - Base Case DCGLs (DCGLB) from LTP Chapter 5, Table 5-3 Turbine Building Radionuclide DCGLB (pCi/m2)
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| Co-60 7.03E+07 Ni-63 2.18E+09 Sr-90 7.74E+05 Cs-134 1.59E+07 Cs-137 2.11E+07 Each radionuclide-specific Base Case DCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem per year to an Average Member of the Critical Group (AMCG). To ensure that the summation of dose from each
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| [12]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 source term is 25 mrem/yr or less after all FSS is completed, the Base Case DCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/year dose limit from each source term. The reduced DCGLs, or Operational DCGLs can be related to the Base Case DCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge and the extent of planned remediation. The Operational DCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the Operational DCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in TSD 17-004. The Operational DCGLB for FSS of the Unit 1 East and West Valve Houses are provided in Table 3.
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| Table 3 - Operational DCGLs (DCGLB) from LTP Chapter 5, Table 5-4 Turbine Building Radionuclide DCGLB (pCi/m2)
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| Co-60 5.98E+06 Ni-63 1.85E+08 Sr-90 6.58E+04 Cs-134 1.35E+06 Cs-137 1.79E+06 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. The Canberra ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. Response checks were required prior to issuance and after each use. Control and accountability of ISOCS units was required to assure data quality.
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| As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than Minimum Detectable Concentration (MDC). Negative values were recorded as zero. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC.
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| In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the Operational DCGL were preferable while MDCs up to 50% of the Operational DCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50 percent of the applicable Operational DCGL.
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| [13]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
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| : 5. SURVEY DESIGN Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001. The Canberra ISOCS was selected as the primary instrument for performing FSS of basement surfaces. The ISOCS was selected as the instrument of choice to perform FSS of basement surfaces due to the fact that an ISOCS measurement will provide results that can be used directly to determine total activity with depth in concrete and, the surface area covered by a single ISOCS measurement is large (a nominal FOV of 10-30 m2) which essentially eliminates the need for a scan surveys. In addition, after an ISOCS measurement is collected, it can be tested against a variety of geometry assumptions to address uncertainty in the source term geometry if necessary.
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| The source term geometry for ISOCS efficiency calibration, (i.e., concentration depth profile and areal distribution of the residual radioactivity in structures), is required to generate efficiency curves (i.e., efficiency as a function of energy) for the ISOCS gamma spectroscopy measurements. The ISOCS efficiency calibration basis chosen for the FSS of the Main Steam Valve Houses concrete are documented in ZionSolutions TSD 14-022.
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| The ISOCS geometry utilized for the Main Steam Valve Houses employed a 28 m2 FOV.
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| A second geometry employing a 2.5 meter stand-off was also used. The selection of this latter geometry was necessitated in situations where there was limited accessibility due to structural constraints.
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| Sample size determination for the FSS of Turbine Building basement is addressed in LTP Chapter 5, section 5.5.2.2. The surface areas of the Main Steam Valve Houses were not originally included in the Turbine Building basement survey unit. Consequently, the weighted average of the ISOCS measurements taken in the Main Steam Valve Houses will be added to the systematic mean of the Turbine Building Basement FSS. This is addressed in LTP Chapter 5, section 5.5.6.1. The total basement area used in the weighted average calculation is the adjusted surface area used to calculate the DCGLs in LTP Chapter 6, section 6.6.8. The adjusted area for the Turbine Building from LTP Chapter 5, Table 5-23 is 27,135 m2. In accordance with TSD 14-014, End State Surface Areas Volumes and Source Terms of Ancillary Bldgs, (Reference 10), the total surface area of each of the two Unit 1 Main Steam Valve Houses is 304 m2 This sample plan for each of the Unit 1 East and West Main Steam Valve Houses consisted of twenty-six (26) systematic measurement/sample locations, ensuring 100%
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| areal coverage of the surface area. Figures 4 and 5 in this record, and in Attachment 1, Figures and Maps, illustrate the locations of the ISOCS measurements taken.
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| The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134, Cs-137 would be the ROC in Survey Units #B1-06213 and #B1-06214. During FSS, concentrations of Hard-to-Detect (HTD) ROC Ni-63 and Sr-90 are inferred using a surrogate approach as
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| [14]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 specified in LTP section 5.2.11. Cs-137 is the principle surrogate radionuclide for Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios were calculated from Auxiliary Building basement concrete core sample analytical results collected and presented in in TSD 14-019 and LTP Chapter 5, Table 5-15, which is reproduced in Table 4 below.
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| Table 4 - Surrogate Ratios Auxiliary Building Ratios Mean Max 95%UCL Ni-63/Co-60 44.143 180.450 154.632 Sr-90/Cs-137 0.001 0.002 0.002 For the FSS of Survey Units #B1-06213 and #B1-06214, the surrogate Operational DCGLs for Co-60 and Cs-137 are based on the maximum ratios from Table 4.
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| Equation 1 1
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| =
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| 1 2 3
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| + + +
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| 2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the Operational DCGLs for the Turbine Building presented in Table 3 and the maximum ratios from Table 4, the following surrogate calculations were performed for FSS Units #B1-06213 and #B1-06214; Equation 2 1
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| (137) = = 1.70 + 06 /2 1 0.002
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| +
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| 1.79 + 06(137) 6.58 + 04(90)
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| The surrogate Operational DCGL that was used for Cs-137 in FSS Units #B1-06213 and
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| #B1-06214 for direct comparison of sample results to demonstrate compliance is 1.70E+06 Ci/m2.
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| Equation 3
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| [15]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 1
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| (60) = = 8.75 + 05 /2 1 180.45
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| +
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| 5.98 + 06(60) 1.85 + 08(63)
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| The surrogate Operational DCGL that was used for Co-60 in FSS Units #B1-06213 and
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| #B1-06214 for direct comparison of sample results to demonstrate compliance is 8.75E+05 Ci/m2.
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| For these Class 1 basement structure survey units, the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-25 and are reproduced below in Table 5.
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| Table 5 - Investigation Levels Classification Direct Investigation Levels Class 1 >Operational DCGLW In compliance with ZS-LT-01, Quality Assurance Project Plan (QAPP) for Characterization and Final Status Survey (Reference 11), replicate measurements were to be performed on 5% of the static measurement locations.
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| Table 6 provides a synopsis of the survey design for Survey Units #B1-06213 and #B1-06214.
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| [16]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Table 6 - Synopsis of the Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Area 304 m2 LTP Ch. 5, Table 5-23
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| * = 0.3
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| * UBGR = SOF of 1
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| * LBGR = SOF of 0.5 Number of Static 26 (systematic)
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| * Type I error = 0.05 Measurements
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| * Type II error = 0.05
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| * / = 3 (adjusted)
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| * MARSSIM Table 5-5 100% Areal Coverage Measurement Spacing LTP Chapter 5, Sec. 5.5.2.2 (Planned for 28 m2 FOV)
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| * Co 5.98E+06 pCi/m2 Operational DCGLs for Turbine
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| * Ni 1.85E+08 pCi/m2 Building Basement OpDCGLB
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| * Sr 6.58E+04 pCi/m2 Unit 1 East Main Steam Valve
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| * Cs-134 - 1.35E+06 pCi/m2 House , (LTP Chapter 5, Table 5-4)
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| * Cs-137 - 1.79E+06 pCi/m2 3 Concrete Core samples selected for HTD HTD ROC Analysis (LTP Chapter 5, section 5.1)
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| ROC analysis Measurement
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| >Operational DCGLW (LTP Chapter 5, Table 5-25)
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| Investigation Level Scan Survey Area ZS-LT-300-001-001, 304 m2 100% areal scan coverage Coverage Attachment 1 QC 5% Duplicate ISOCS Measurements (LTP Chapter 5, section 5.9)
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| [17]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
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| : 6. SURVEY IMPLEMENTATION For the systematic measurements performed in Survey Units #B1-06213 and #B1-06214, compliance with the unrestricted release criteria was demonstrated through a combination of direct measurements using the ISOCS and analysis of concrete core samples obtained from the Main Steam Valve Houses. The concrete core data was used to validate the ratios of gamma emitters to HTD ROC.
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| A walk down was performed by FSS personnel on 04/18/18. A turnover survey and groundwater pump out was required to permit acceptance of the Main Steam Valve House survey units for FSS. Characterization data from 2012 and 2013, including 10 concrete core samples did not identify any conditions precluding turnover, however turnover surveys were utilized to confirm demolition work in the area had not altered conditions. The Main Steam Valve Houses were deemed acceptable for turnover and FSS commenced on 04/25/18.
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| Field Logs (ZS-LT-300-001-001 Attachment 14) were used to document field activities and other information pertaining to the performance of the FSS. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job.
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| ZionSolutions TSD 14-022 provides the initial justification for the selection of reasonably conservative geometries and efficiency calibrations for the ISOCS based on the physical conditions of the remediated surface and the anticipated depth and distribution of activity.
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| All ISOCS measurements were acquired using an approved geometry. One source to detector distance was utilized to ensure 100% measurement coverage. The primary ISOCS geometry utilized was 3M90D_CP_2IN, and is described in detail in Attachment 3.
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| The ISOCS detector was positioned horizontally or vertically to the surface at the center-point of each selected measurement location. The exposed face of the detector was positioned at a distance of 3 meters from the surface with the 90- degree collimation shield installed; this orientation corresponded to a nominal FOV of 28 m2 for walls The measured activity for each gamma-emitting ROC (and any other gamma emitting radionuclides positively detected by ISOCS) was recorded in units of pCi/m2.
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| Background was not subtracted from any measurement. A SOF calculation was performed for each measurement by dividing the reported concentration of each ROC by the Operational DCGL for each ROC to derive an individual ROC fraction. The individual ROC fractions were then summed to provide a total SOF value for the measurement.
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| Two (2) duplicate measurements were taken with the ISOCS on each of the two Unit 1 Valve House during FSS. The locations selected for taking duplicate measurements were
| |
| [18]
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| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 at locations 002 and 020 in the East Valve house, and at locations 007 and 016 in the West Valve House. These locations were randomly selected using the Microsoft Excel RANDBETWEEN function. The number of replicate measurements satisfies the requirement that a minimum of 5% percent of the number of measurements that will be used for duplicate samples in accordance with ZSRP-QAPP.
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| : 7. SURVEY RESULTS The SOF or unity rule was applied to the data used for the survey planning, data evaluation and statistical tests for basement surfaces since multiple radionuclide-specific measurements were performed and concentrations inferred based on known relationships.
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| The application of the unity rule served to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule was applied, the DCGLw (used for the nonparametric statistical test) becomes one (1).
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| The Base Case basement structure DCGLs (BcDCGLB), was directly analogous to the DCGLW as defined in MARSSIM. The use and application of the unity rule was performed in accordance with section 4.3.3 of MARSSIM.
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| For building surfaces, areas of elevated activity were defined as any area identified by measurement/sample (systematic or judgmental) that exceeded the Operational DCGL but was less than the Base Case DCGL. Any area that exceeded the Base Case DCGL would have required remediation. ISOCS measurements indicated the OpSOF exceeded one for 2 of the 26 measurements taken in the Unit 1 East Valve House, and one of the 26 measurements taken in the Unit 1 West Valve House. The result of all ISOCS measurements taken in both Valve Houses were below the BcDCGLs.
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| The sample population consisted of twenty-six (26) direct measurements for each of the Unit 1 Valve houses and measurements were acquired using the ISOCS. The concentrations for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The complete ISOCS gamma spectroscopy reports are presented in Attachment 6. The ISOCS measured concentration results from the Unit 1 East Valve House are listed in Table 7.
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| Direct measurement locations were denoted on the concrete surfaces of the Unit 1 East and West Valve Houses by marking an approximate 4 meter by 4 meter grid pattern using a random start point that was overlaid over the exposed surface, providing sufficient overlap between locations to ensure 100% areal coverage. ISOCS measurement locations are shown below in Figures 4 and 5 as well as in Attachment 1.
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| [19]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Figure 4 - Unit 1 East Main Steam Valve House ISOCS Survey and Sample Map
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| [20]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Figure 5 - Unit 1 West Main Steam Valve House ISOCS Survey and Sample Map
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| [21]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Table 7 - Unit 1 East Main Steam Valve House- ISOCS Results for FSS Co-60 Cs-134 Cs-137 Ni-63 Sr-90 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)
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| B3-6213AF-SFC-001-GD 2.42E+04 3.88E+04 1.51E+06 4.37E+06 3.02E+03 0.9459 B3-6213AF-SFC-002-GD 3.75E+03 6.71E+04 7.06E+06 6.77E+05 1.41E+04 4.2127 B3-6213AF-SFC-003-GD 1.99E+04 2.33E+04 1.58E+06 3.59E+06 3.16E+03 0.9707 B3-6213AF-SFC-004-GD 1.98E+04 4.66E+04 7.55E+05 3.57E+06 1.51E+03 0.5019 B3-6213AF-SWC-005-GD 3.52E+02 5.04E+03 6.85E+04 6.35E+04 1.37E+02 0.0445 B3-6213AF-SWC-006-GD 9.10E+02 2.19E+04 4.07E+04 1.64E+05 8.14E+01 0.0412 B3-6213AF-SWC-007-GD 3.40E+04 7.80E+04 2.93E+04 6.14E+06 5.86E+01 0.1139 B3-6213AF-SWC-008-GD 3.13E+04 5.45E+03 3.07E+04 5.65E+06 6.14E+01 0.0579 B3-6213AF-SWC-009-GD 2.69E+04 3.48E+04 1.13E+05 4.85E+06 2.26E+02 0.1231 B3-6213AF-SWC-010-GD 0.00E+00 2.75E+04 4.50E+05 0.00E+00 9.00E+02 0.2854 B3-6213AF-SWC-011-GD 3.34E+04 4.33E+04 2.12E+04 6.03E+06 4.24E+01 0.0827 B3-6213AF-SWC-012-GD 4.69E+03 8.07E+04 0.00E+00 8.46E+05 0.00E+00 0.0651 B3-6213AF-SWC-013-GD 1.85E+04 1.89E+04 1.45E+05 3.34E+06 2.90E+02 0.1206 B3-6213AF-SWC-014-GD 2.98E+04 4.40E+04 3.30E+05 5.38E+06 6.60E+02 0.2610 B3-6213AF-SWC-015-GD 1.20E+04 5.12E+04 3.97E+04 2.17E+06 7.94E+01 0.0750 B3-6213AF-SWC-016-GD 2.10E+04 4.74E+04 2.72E+04 3.79E+06 5.44E+01 0.0751 B3-6213AF-SWC-017-GD 0.00E+00 4.09E+04 2.52E+06 0.00E+00 5.04E+03 1.5147 B3-6213AF-SWC-018-GD 4.26E+04 3.69E+03 5.55E+05 7.69E+06 1.11E+03 0.3783 B3-6213AF-SWC-019-GD 2.12E+04 6.66E+04 4.08E+04 3.83E+06 8.16E+01 0.0976 B3-6213AF-SWC-020-GD 0.00E+00 2.97E+04 1.89E+05 0.00E+00 3.78E+02 0.1333 B1-6213AF-SWC-021-GD 1.46E+04 1.59E+03 9.72E+05 2.63E+06 1.94E+03 0.5904 B1-6213AF-SWC-022-GD 7.08E+03 5.28E+04 3.87E+05 1.28E+06 7.74E+02 0.2752 B1-6213AF-SWC-023-GD 5.24E+03 6.51E+03 4.25E+05 9.46E+05 8.50E+02 0.2612 B1-6213AF-SWC-024-GD 0.00E+00 3.26E+04 8.36E+04 0.00E+00 1.67E+02 0.0734 B1-6213AF-SWC-025-GD 0.00E+00 4.32E+04 1.50E+05 0.00E+00 3.00E+02 0.1204 B1-6213AF-SWC-026-GD 1.79E+04 4.17E+04 3.06E+05 3.23E+06 6.12E+02 0.2316 Twenty-six (26) ISOCS measurements were taken in the Unit 1 East Main Steam Valve House. Of the 26 measurements, two measurements exceeded a OpSOF of one when compared to the Operational DCGLs. The mean OpSOF was 0.4482 and the max OpSOF was 4.2127.
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| In order to assess the dose contribution from the Unit 1 East Main Steam Valve House, the concentration of each ROC in each judgmental measurement was also compared against the respective Base Case DCGLs. The calculation of the mean BcSOF for the Unit 1 East Main Steam Valve House and the resultant dose is presented in Table 8.
| |
| [22]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Table 8 - Basic Statistical Properties of ISOCS Measurements in the Unit 1 East Main Steam Valve House Mean Median Max Min BcDCGL Avg. SOF Avg. Dose ROC Std. Dev.
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| (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC Per ROC Co-60 1.50E+04 1.63E+04 4.26E+04 0.00E+00 1.30E+04 7.07E+07 0.0002 0.0053 Cs-134 3.67E+04 3.99E+04 8.07E+04 1.59E+03 2.23E+04 1.59E+07 0.0023 0.0576 Cs-137 6.86E+05 1.70E+05 7.06E+06 0.00E+00 1.43E+06 2.11E+07 0.0325 0.8125 Ni-63 2.70E+06 2.93E+06 7.69E+06 0.00E+00 2.35E+06 2.18E+09 0.0012 0.0310 Sr-90 1.37E+03 3.39E+02 1.41E+04 0.00E+00 2.87E+03 7.74E+05 0.0018 0.0443 The mean BcSOF from measurements taken on basement structural surfaces in the Unit 1 East Main Steam Valve House is 0.0380. This is derived by summing the average SOF per ROC resulting from the average concentration in Table 8. Using Equation 5-5 from LTP Chapter 5, section 5.5.4, the adjustment to the mean BcSOF from elevated measurements #B3-6213AF-SFC-002-GD and #B3-6213AF-SWC-017-GD is 0.0378.
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| The adjusted mean BcSOF for the Unit 1 East Main Steam Valve House is 0.0758, which equates to a dose of 1.8945 mrem/yr.
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| The ISOCS measured concentration results from the Unit 1 West Valve House are listed in Table 9.
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| Table 9 - Unit 1 West Main Steam Valve House- ISOCS Results for FSS Co-60 Cs-134 Cs-137 Ni-63 Sr-90 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)
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| B1-6214AF-SFC-001-GD 2.56E+04 0.00E+00 7.04E+05 4.62E+06 1.41E+03 0.4439 B1-6214AF-SFC-002-GD 0.00E+00 5.42E+04 2.60E+05 0.00E+00 5.20E+02 0.1933 B1-6214AF-SFC-003-GD 2.98E+04 6.33E+04 8.58E+05 5.38E+06 1.72E+03 0.5863 B1-6214AF-SFC-004-GD 2.84E+04 0.00E+00 3.03E+06 5.12E+06 6.06E+03 1.8173 B1-6214AF-SWC-005-GD 2.74E+04 7.01E+04 1.29E+06 4.94E+06 2.58E+03 0.8431 B1-6214AF-SWC-006-GD 1.10E+04 3.86E+04 4.43E+04 1.98E+06 8.86E+01 0.0673 B1-6214AF-SWC-007-GD 2.98E+04 3.79E+04 2.86E+04 5.38E+06 5.72E+01 0.0790 B1-6214AF-SWC-008-GD 2.98E+04 6.00E+04 1.77E+05 5.38E+06 3.54E+02 0.1828 B1-6214AF-SWC-009-GD 1.46E+04 6.10E+04 5.05E+04 2.63E+06 1.01E+02 0.0916 B1-6214AF-SWC-010-GD 3.91E+03 2.02E+04 3.41E+04 7.06E+05 6.82E+01 0.0395 B1-6214AF-SWC-011-GD 7.23E+03 1.42E+04 2.97E+04 1.30E+06 5.94E+01 0.0363 B1-6214AF-SWC-012-GD 1.85E+04 7.88E+04 3.24E+04 3.34E+06 6.48E+01 0.0986 B1-6214AF-SWC-013-GD 0.00E+00 5.16E+04 3.65E+04 0.00E+00 7.30E+01 0.0597 B1-6214AF-SWC-014-GD 1.01E+03 4.05E+04 4.00E+04 1.82E+05 8.00E+01 0.0547 B1-6214AF-SWC-015-GD 6.04E+03 2.07E+04 3.13E+04 1.09E+06 6.26E+01 0.0407 B1-6214AF-SWC-016-GD 1.04E+04 6.59E+04 1.79E+05 1.88E+06 3.58E+02 0.1661 B1-6214AF-SWC-017-GD 1.12E+04 1.81E+04 1.19E+05 2.02E+06 2.38E+02 0.0963 B1-6214AF-SWC-018-GD 1.14E+04 5.58E+04 3.11E+04 2.06E+06 6.22E+01 0.0727 B1-6214AF-SWC-019-GD 1.99E+04 9.19E+04 4.66E+04 3.59E+06 9.32E+01 0.1183 B1-6214AF-SWC-020-GD 1.56E+04 3.72E+04 1.70E+05 2.82E+06 3.40E+02 0.1455 B1-6214AF-SWC-021-GD 0.00E+00 3.22E+04 1.82E+05 0.00E+00 3.64E+02 0.1311
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| [23]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Table 9 (continued) - Unit 1 West Main Steam Valve House- ISOCS Results for FSS Co-60 Cs-134 Cs-137 Ni-63 Sr-90 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)
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| B1-6214AF-SWC-022-GD 2.80E+04 6.97E+04 1.31E+05 5.05E+06 2.62E+02 0.1608 B1-6214AF-SWC-023-GD 1.99E+04 4.16E+04 4.76E+04 3.59E+06 9.52E+01 0.0816 B1-6214AF-SWC-024-GD 3.41E+04 0.00E+00 2.13E+05 6.15E+06 4.26E+02 0.1644 B1-6214AF-SWC-025-GD 2.84E+04 3.97E+04 5.09E+05 5.12E+06 1.02E+03 0.3617 B1-6214AF-SWC-026-GD 5.67E+03 8.11E+04 4.01E+04 1.02E+06 8.02E+01 0.0902 Twenty-six (26) ISOCS measurements were taken in the Unit 1 West Main Steam Valve House. Of the 26 measurements, one measurement exceeded a OpSOF of one when compared to the Operational DCGLs. The mean OpSOF was 0.2393 and the max OpSOF was 1.8173.
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| In order to assess the dose contribution from the Unit 1 West Main Steam Valve House, the concentration of each ROC in each judgmental measurement was also compared against the respective Base Case DCGLs. The calculation of the mean BcSOF for the Circulating Water Discharge Tunnels and the resultant dose is presented in Table 10.
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| Table 10 - Basic Statistical Properties of ISOCS Measurements in the Unit 1 West Main Steam Valve House Mean Median Max Min BcDCGL Avg. SOF Avg. Dose ROC Std. Dev.
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| (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC Per ROC Co-60 1.61E+04 1.51E+04 3.41E+04 0.00E+00 1.12E+04 7.07E+07 0.0002 0.0057 Cs-134 4.40E+04 4.11E+04 9.19E+04 0.00E+00 2.58E+04 1.59E+07 0.0028 0.0692 Cs-137 3.20E+05 8.48E+04 3.03E+06 2.86E+04 6.31E+05 2.11E+07 0.0152 0.3789 Ni-63 2.90E+06 2.72E+06 6.15E+06 0.00E+00 2.02E+06 2.18E+09 0.0013 0.0332 Sr-90 6.40E+02 1.70E+02 6.06E+03 5.72E+01 1.26E+03 7.74E+05 0.0008 0.0207 The mean BcSOF from measurements taken on basement structural surfaces in the Unit 1 East Main Steam Valve House is 0.0203. This is derived by summing the average SOF per ROC resulting from the average concentration in Table 8. Using Equation 5-5 from LTP Chapter 5, section 5.5.4, the adjustment to the mean BcSOF from elevated measurement # B1-6214AF-SFC-004-GD is 0.0123. The adjusted mean BcSOF for the Unit 1 West Main Steam Valve House is 0.0326, which equates to a dose of 0.8160 mrem/yr.
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| Six (6) concrete core samples, three for each Valve House, were acquired at 10% of the locations where ISOCS measurements were collected with the locations selected at random. The first top 1/2 inch puck from each concrete core sample, representing the concrete from the exposed surface to a depth of 1/2 inch were analyzed, were counted at an off-site laboratory (Eberline) for gamma emitters and HTDs to confirm the surrogate ROCs.
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| [24]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 The results of the analysis of concrete core samples taken in the Unit 1 East Main Steam Valve House is presented in Table 11 below; Table 11 - FSS Concrete Core Taken in East Main Steam Valve House Analysis by Eberline B1-06213A-FSFC-002CV ROC Result Uncertainty MDC Co-60 8.50E-03 5.49E-02 7.82E-02 Ni-63 3.18E+00 1.12E+00 1.80E+00 Sr-90 7.28E-02 2.27E-01 4.77E-01 Cs-134 0.00E+00 6.82E-02 1.10E-01 Cs-137 9.24E+01 9.00E+00 3.04E-01 B1-06213A-FSFC-004CV ROC Result Uncertainty MDC Co-60 0.00E+00 7.29E-02 9.75E-02 Ni-63 1.00E+00 9.70E-01 1.62E+00 Sr-90 3.63E-01 2.20E-01 4.29E-01 Cs-134 1.45E-03 3.33E-02 1.07E-01 Cs-137 1.07E+00 2.02E-01 2.24-01 B1-06213A-FSWC-009CV ROC Result Uncertainty MDC Co-60 5.16E-02 1.09E-01 1.83E-01 Ni-63 5.96E-01 1.07E+00 1.82E+00 Sr-90 3.61E-01 2.75E-01 4.98E-01 Cs-134 7.41E-03 6.93E-02 1.91E-01 Cs-137 6.95E-02 1.51E-01 2.31E-01 In the three concrete core samples taken in the Unit 1 East Valve House, one or more of each ROC (Co-60, Ni-63, Sr-90, Cs-137) was less than MDC. Consequently, there was no compelling evidence to challenge the HTD ratios specified in the LTP and presented in Table 4. The results of the analysis of concrete core samples taken in the Unit 1 West Main Steam Valve House is presented in Table 12 below; Table 12 - FSS Concrete Core Taken in West Main Steam Valve House Analysis by Eberline B1-06214A-FSFC-001CV ROC Result Uncertainty MDC Co-60 6.87E-02 9.05E-02 1.66E-01 Ni-63 6.77E-01 1.08E+00 1.83E+00 Sr-90 8.14E-01 2.35E-01 4.06E-01 Cs-134 0.00E+00 8.90E-02 1.94E-01 Cs-137 1.06E+01 3.00E+01 1.37E+00
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| [25]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Table 12 (continued) - FSS Concrete Core Taken in West Main Steam Valve House Analysis by Eberline B1-06214A-FSFC-004CV ROC Result Uncertainty MDC Co-60 0.00E+00 1.03E-01 1.45E-01 Ni-63 2.07E+00 1.10E+00 1.80E+00 Sr-90 4.17E-01 2.46E-01 4.81E-01 Cs-134 2.76E-02 7.97E-02 1.78E-01 Cs-137 4.16E+01 4.13E+00 3.77E-01 B1-06214A-FSWC-005CV ROC Result Uncertainty MDC Co-60 4.21E-02 1.42E-01 2.26E-01 Ni-63 2.09E-01 9.98E-01 1.70E+00 Sr-90 2.61E-01 2.33E-01 4.69E-01 Cs-134 0.00E+00 3.60E-01 2.24E-01 Cs-137 1.33E+00 3.29E-01 3.96E-01 All units in pCi/g In two of the three concrete core samples taken from Unit 1 West Main Valve House, one or more of each ROC (Co-60, Ni-63 and/or Sr-90) was less than MDC. A single positive Sr-90 result at location B1-06214A-FSFC-001-CV was just above the MDC, resulting in a Sr-90 to Cs-137 ratio higher than that specified in Table 4 (0.077 vs. 0.002). This result is believed to be an unreliable outlier due to its proximity to the analytical MDC for both components and was not used. Again, there is no compelling evidence that would challenge the surrogate ratios utilized for this survey unit.
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| : 8. QUALITY CONTROL The implementation of required QC measures included the collection of two (2) additional ISOCS measurements each of the Unit 1 East and Unit 1 West Valve Houses (Survey Units #B1-06213 and #B1-06214) for replicate measurement analysis. The concentrations for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The replicate ISOCS measurement results are presented in Table 13 for Unit 1 East Valve House, and Table 14 for Unit 1 West Valve House.
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| Table 13 - Summary of ISOCS Replicate Measurements for QC Unit 1 East Valve House Co-60 Cs-134 Cs-137 Ni-63 Sr-90 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)
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| B3-6215AF-QFC-002-GD 2.10E+03 0.00E+00 7.04E+06 3.79E+05 1.41E+04 4.1493 B3-6215AF-QWC-020-GD 1.43E+04 5.45E+04 1.22E+05 2.58E+06 2.44E+02 0.1286
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| [26]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Table 14 - Summary of ISOCS Replicate Measurements for QC Unit 1 West Valve House Co-60 Cs-134 Cs-137 Ni-63 Sr-90 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)
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| B1-6214AF-QWC-007-GD 3.41E+04 3.19E+03 2.85E+04 6.15E+06 5.70E+01 0.0581 B1-6214AF-QWC-016-GD 1.04E+04 2.72E+04 2.13E+05 1.88E+06 4.26E+02 0.1575 The complete ISOCS gamma spectroscopy reports for the duplicate measurements are presented in Attachment 4. All duplicate ISOCS measurements met the required acceptance criteria.
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| : 9. INVESTIGATION AND RESULTS No measurements were taken for an investigation during the performance of FSS in this survey unit.
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| : 10. REMEDIATION AND RESULTS No remediation was required prior to performance of FSS.
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| : 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN The survey design for this FSS was revised based on a change in classification. During the performance of the initial survey, FSS results indicated radiological concentrations in excess of 50% of the OpDCGL with several measurements exceeding the OpDCGLs.
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| Consequently, the survey unit was reclassified as Class 1 and the survey design was revised accordingly.
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| In addition, there were changes to the ISOCS survey plans as noted. Those changes were required due to structural interferences restricting placement of the ISOCS detector that were not obvious when the FSS plan was first written. The changes in ISOCS measurement locations were made to ensure 100% areal coverage of the survey unit.
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| : 12. DATA QUALITY ASSESSMENT (DQA)
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| The DQO sample design and data were reviewed in accordance with ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 12),
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| for completeness and consistency. Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 1.
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| The preliminary data review consisted of calculating basic statistical quantities (e.g.,
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| mean, median, standard deviation). All data was considered valid and the values reported below the MDC, and values with uncertainties that exceeded two standard deviations.
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| All measurement results were individually reviewed and validated. The FOV for the number of measurements taken was sufficient to meet the requirement of 100% areal
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| [27]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 coverage of surfaces for a Class 1 survey unit. The instrumentation used to perform the FSS were in calibration, capable of detecting the activity with an adequate MDC and successfully response checked prior to and following use. An adequate number of replicate measurements were taken and the results meet the acceptance criteria as specified in the QAPP.
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| The analytical results for 49 of the 52 ISOCS measurements taken were less than a SOF of one when directly compared against the OpDCGL. Three ISOCS measurements exceeded the OpDCGL but were less than the BcDCGLs.
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| : 13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.
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| : 14. CONCLUSION A total of 52 ISOCS measurements were taken in the Unit 1 East and West Main Steam Valve Houses (26 ISOCS measurements in each). The FOV for the Circular Plan geometry used for the majority of the ISOCS measurements was 28 m2, which equated to an areal coverage 100% of the surface area (including the floor and the 5 walls) of the Unit 1 East and West Main Steam Valve Houses. The total surface area for each Valve House was 304 m2.
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| ISOCS measurements indicated the OpSOF exceeded one for 2 of the 26 measurements taken in the Unit 1 East Valve House and one of the 26 measurements taken in the Unit 1 West Valve house. All results for both Valve Houses were below the Base Case DCGLs.
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| The mean BcSOF for each ROC was less than their respective Base Case DCGLs. In addition, the measurements results in both Valve Houses passed the Sign Test. The mean BcSOF for Survey Unit #B1-06213, adjusted for the dose from the two elevated measurements was 0.0758, which equates to a dose of 1.8945 mrem/yr. The mean BcSOF for Survey Unit #B1-06214, adjusted for the dose from the one elevated measurement was 0.0326, which equates to a dose of 0.8160 mrem/yr.
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| Survey Units # B1-06213 and # B1-06214 are acceptable for unrestricted release.
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| : 15. REFERENCES
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| : 1. ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting
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| : 2. Zion Station Restoration Project License Termination Plan
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| : 3. ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development
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| [28]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
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| : 4. NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)
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| : 5. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey
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| : 6. ZionSolutions TSD 14-022 Revision 2, Use of In-Situ Gamma Spectroscopy for Source Term Survey of End State Structures
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| : 7. ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification
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| : 8. Zion Station Historical Site Assessment (HSA)
| |
| : 9. ZionSolutions TSD 11-001, Potential Radionuclides of Concern during the Decommissioning of Zion Station
| |
| : 10. ZionSolutions TSD 14-014, End State Surface Areas Volumes and Source Terms of Ancillary Bldgs
| |
| : 11. ZionSolutions ZS-LT-01, Quality Assurance Project Plan (QAPP) for Characterization and Final Status Survey
| |
| : 12. ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment
| |
| : 16. ATTACHMENTS Attachment 1 - Figure and Maps Attachment 2 - ISOCS Geometry Attachment 3 - Sign Test Attachment 4 - QC Measurement Assessments Attachment 5 - Eberline Report Attachment 6 - ISOCS Analytical Reports
| |
| [29]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ATTACHMENT 1 FIGURES AND MAPS
| |
| [30]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Figure 1 - Overview of Structural Survey Unit
| |
| [31]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [32]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ATTACHMENT 2 ISOCS GEOMETRY
| |
| [33]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [34]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [35]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [36]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [37]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [38]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214
| |
| [39]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ATTACHMENT 3 SIGN TEST
| |
| [40]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Sign Test - Unit 1 East Main Steam Valve House Co-60 Cs-134 Cs-137 Ni-63 Sr-90 SOF No. 1-Ws Sign SOF SOF SOF SOF SOF (Ws) 1 2.42E+04 3.88E+04 1.51E+06 4.37E+06 3.02E+03 0.9459 0.054 +
| |
| 2 3.75E+03 6.71E+04 7.06E+06 6.77E+05 1.41E+04 4.2127 -3.213 -
| |
| 3 1.99E+04 2.33E+04 1.58E+06 3.59E+06 3.16E+03 0.9707 0.029 +
| |
| 4 1.98E+04 4.66E+04 7.55E+05 3.57E+06 1.51E+03 0.5019 0.498 +
| |
| 5 3.52E+02 5.04E+03 6.85E+04 6.35E+04 1.37E+02 0.0445 0.956 +
| |
| 6 9.10E+02 2.19E+04 4.07E+04 1.64E+05 8.14E+01 0.0412 0.959 +
| |
| 7 3.40E+04 7.80E+04 2.93E+04 6.14E+06 5.86E+01 0.1139 0.886 +
| |
| 8 3.13E+04 5.45E+03 3.07E+04 5.65E+06 6.14E+01 0.0579 0.942 +
| |
| 9 2.69E+04 3.48E+04 1.13E+05 4.85E+06 2.26E+02 0.1231 0.877 +
| |
| 10 0.00E+00 2.75E+04 4.50E+05 0.00E+00 9.00E+02 0.2854 0.715 +
| |
| 11 3.34E+04 4.33E+04 2.12E+04 6.03E+06 4.24E+01 0.0827 0.917 +
| |
| 12 4.69E+03 8.07E+04 0.00E+00 8.46E+05 0.00E+00 0.0651 0.935 +
| |
| 13 1.85E+04 1.89E+04 1.45E+05 3.34E+06 2.90E+02 0.1206 0.879 +
| |
| 14 2.98E+04 4.40E+04 3.30E+05 5.38E+06 6.60E+02 0.2610 0.739 +
| |
| 15 1.20E+04 5.12E+04 3.97E+04 2.17E+06 7.94E+01 0.0750 0.925 +
| |
| 16 2.10E+04 4.74E+04 2.72E+04 3.79E+06 5.44E+01 0.0751 0.925 +
| |
| 17 0.00E+00 4.09E+04 2.52E+06 0.00E+00 5.04E+03 1.5147 -0.515 -
| |
| 18 4.26E+04 3.69E+03 5.55E+05 7.69E+06 1.11E+03 0.3783 0.622 +
| |
| 19 2.12E+04 6.66E+04 4.08E+04 3.83E+06 8.16E+01 0.0976 0.902 +
| |
| 20 0.00E+00 2.97E+04 1.89E+05 0.00E+00 3.78E+02 0.1333 0.867 +
| |
| 21 1.46E+04 1.59E+03 9.72E+05 2.63E+06 1.94E+03 0.5904 0.410 +
| |
| 22 7.08E+03 5.28E+04 3.87E+05 1.28E+06 7.74E+02 0.2752 0.725 +
| |
| 23 5.24E+03 6.51E+03 4.25E+05 9.46E+05 8.50E+02 0.2612 0.739 +
| |
| 24 0.00E+00 3.26E+04 8.36E+04 0.00E+00 1.67E+02 0.0734 0.927 +
| |
| 25 0.00E+00 4.32E+04 1.50E+05 0.00E+00 3.00E+02 0.1204 0.880 +
| |
| 26 1.79E+04 4.17E+04 3.06E+05 3.23E+06 6.12E+02 0.2316 0.768 +
| |
| Number of Measurements = 26 Type I Error = .05 Number of Positive Differences (S+) = 24 Critical Value = 17 Survey unit MEETS the Acceptance Criteria Yes
| |
| [41]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Sign Test - Unit 1 West Main Steam Valve House Co-60 Cs-134 Cs-137 Ni-63 Sr-90 SOF No. 1-Ws Sign SOF SOF SOF SOF SOF (Ws) 1 2.56E+04 0.00E+00 7.04E+05 4.62E+06 1.41E+03 0.4439 0.556 +
| |
| 2 0.00E+00 5.42E+04 2.60E+05 0.00E+00 5.20E+02 0.1933 0.807 +
| |
| 3 2.98E+04 6.33E+04 8.58E+05 5.38E+06 1.72E+03 0.5863 0.414 +
| |
| 4 2.84E+04 0.00E+00 3.03E+06 5.12E+06 6.06E+03 1.8173 -0.817 -
| |
| 5 2.74E+04 7.01E+04 1.29E+06 4.94E+06 2.58E+03 0.8431 0.157 +
| |
| 6 1.10E+04 3.86E+04 4.43E+04 1.98E+06 8.86E+01 0.0673 0.933 +
| |
| 7 2.98E+04 3.79E+04 2.86E+04 5.38E+06 5.72E+01 0.0790 0.921 +
| |
| 8 2.98E+04 6.00E+04 1.77E+05 5.38E+06 3.54E+02 0.1828 0.817 +
| |
| 9 1.46E+04 6.10E+04 5.05E+04 2.63E+06 1.01E+02 0.0916 0.908 +
| |
| 10 3.91E+03 2.02E+04 3.41E+04 7.06E+05 6.82E+01 0.0395 0.961 +
| |
| 11 7.23E+03 1.42E+04 2.97E+04 1.30E+06 5.94E+01 0.0363 0.964 +
| |
| 12 1.85E+04 7.88E+04 3.24E+04 3.34E+06 6.48E+01 0.0986 0.901 +
| |
| 13 0.00E+00 5.16E+04 3.65E+04 0.00E+00 7.30E+01 0.0597 0.940 +
| |
| 14 1.01E+03 4.05E+04 4.00E+04 1.82E+05 8.00E+01 0.0547 0.945 +
| |
| 15 6.04E+03 2.07E+04 3.13E+04 1.09E+06 6.26E+01 0.0407 0.959 +
| |
| 16 1.04E+04 6.59E+04 1.79E+05 1.88E+06 3.58E+02 0.1661 0.834 +
| |
| 17 1.12E+04 1.81E+04 1.19E+05 2.02E+06 2.38E+02 0.0963 0.904 +
| |
| 18 1.14E+04 5.58E+04 3.11E+04 2.06E+06 6.22E+01 0.0727 0.927 +
| |
| 19 1.99E+04 9.19E+04 4.66E+04 3.59E+06 9.32E+01 0.1183 0.882 +
| |
| 20 1.56E+04 3.72E+04 1.70E+05 2.82E+06 3.40E+02 0.1455 0.855 +
| |
| 21 0.00E+00 3.22E+04 1.82E+05 0.00E+00 3.64E+02 0.1311 0.869 +
| |
| 22 2.80E+04 6.97E+04 1.31E+05 5.05E+06 2.62E+02 0.1608 0.839 +
| |
| 23 1.99E+04 4.16E+04 4.76E+04 3.59E+06 9.52E+01 0.0816 0.918 +
| |
| 24 3.41E+04 0.00E+00 2.13E+05 6.15E+06 4.26E+02 0.1644 0.836 +
| |
| 25 2.84E+04 3.97E+04 5.09E+05 5.12E+06 1.02E+03 0.3617 0.638 +
| |
| 26 5.67E+03 8.11E+04 4.01E+04 1.02E+06 8.02E+01 0.0902 0.910 +
| |
| Number of Measurements = 26 Type I Error = .05 Number of Positive Differences (S+) = 25 Critical Value = 17 Survey unit MEETS the Acceptance Criteria Yes
| |
| [42]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ATTACHMENT 4 QC MEASUREMENT ASSESSMENTS
| |
| [43]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Replicate Measurement Assessment Duplicate Sample Assessment Form Survey Area #: 06000 Survey Unit # 06213 Survey Unit Name: U1 Steam Tunnel East VH Sample Plan#: B1-06213-AF Sample
| |
| | |
| == Description:==
| |
| Comparison of systematic and QC ISOCS measurements of concrete wall at location # 002.
| |
| STANDARD COMPARISON Activity Activity Standard Agreement Standard Comparison Acceptable Radionuclide Value Resolution Value Error Range Error Ratio (Y/N)
| |
| (pCi/m2) (pCi/m2)
| |
| Cs-137 7.06E+06 8.68E+05 8 0.6-1.66 7.04E+06 8.66E+05 1.0 Y Comments/Corrective Actions: None Table is provided to show acceptance criteria used to assess split samples.
| |
| Performed by: Robert Massengill Date: Reveiwed by: Date:
| |
| 4/26/2018 4/26/2018
| |
| [44]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Duplicate Sample Assessment Form Survey Area #: 06000 Survey Unit # 06213 Survey Unit Name: U1 Steam Tunnel East VH Sample Plan#: B1-06213-AF Sample
| |
| | |
| == Description:==
| |
| Comparison of systematic and QC ISOCS measurements of concrete wall at location # 020.
| |
| STANDARD COMPARISON Activity Standard Agreement Activity Standard Comparison Acceptable Radionuclide Resolution Value Error Range Value Error Ratio (Y/N)
| |
| Cs-137 1.89E+05 4.15E+04 5 0.6-1.66 1.22E+05 3.05E+04 1.5 Y Comments/Corrective Actions: None Table is provided to show acceptance criteria used to assess split samples.
| |
| [45]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Duplicate Sample Assessment Form Survey Area #: 06000 Survey Unit # 06214 Survey Unit Name: U1 Steam Tunnel West VH Sample Plan#: B1-06214A-F Sample
| |
| | |
| == Description:==
| |
| Comparison of systematic and QC ISOCS measurements of concrete wall at location # 007.
| |
| STANDARD COMPARISON Activity Standard Agreement Activity Standard Comparison Acceptable Radionuclide Resolution Value Error Range Value Error Ratio (Y/N)
| |
| Cs-137 2.86E+04 1.67E+04 2 0.5-2.0 2.85E+04 1.65E+04 1.0 Y Comments/Corrective Actions: None Table is provided to show acceptance criteria used to assess split samples.
| |
| Performed by: Robert Massengill Date: Reveiwed by: Date:
| |
| 5/5/2018 5/5/2018
| |
| [46]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 Duplicate Sample Assessment Form Survey Area #: 06000 Survey Unit # 06214 Survey Unit Name: U1 Steam Tunnel West VH Sample Plan#: B1-06214A-F Sample
| |
| | |
| == Description:==
| |
| Comparison of systematic and QC ISOCS measurements of concrete wall at location # 016.
| |
| STANDARD COMPARISON Activity Activity Standard Agreement Standard Comparison Acceptable Radionuclide Value Resolution Value Error Range Error Ratio (Y/N)
| |
| (pCi/m2) (pCi/m2)
| |
| Cs-137 1.79E+05 3.84E+04 5 0.5-2.0 2.13E+05 4.28E+04 0.8 Y Comments/Corrective Actions: None Table is provided to show acceptance criteria used to assess split samples.
| |
| Performed by: Robert Massengill Date: Reveiwed by: Date:
| |
| 5/5/2018 5/5/2018
| |
| [47]
| |
| | |
| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ATTACHMENT 5 EBERLINE REPORT
| |
| [48]
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| | |
| [49]
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| [72]
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| FSS RELEASE RECORD UNIT 1 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06213 & 06214 ATTACHMENT 6 ISOCS ANALYTICAL REPORTS
| |
| [73]
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